Din avgränsning ger 106 träffar.

• 2011:05 Overview and Evaluation of the NESC Projects for Fracture Assessments of Nuclear Components

  The Network for Evaluation of Structural Components (NESC) was started in 1993 and since then six different projects have been carried out. A seventh NESC-project is still in progress. The overall objective of these projects has been to study the reliability of the entire process of structural

  Innehållstyp: Publikationer

• 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

  During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to

  Innehållstyp: Publikationer

• 2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report

  The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop

  Innehållstyp: Publikationer

• 2010:22 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16

  This report constitutes Stage 16 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 15 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been

  Innehållstyp: Publikationer

• 2010:45 Evaluation of models for cyclic plastic deformation – A literature study

  Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been

  Innehållstyp: Publikationer

• 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

  In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to

  Innehållstyp: Publikationer

• 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

  No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and

  Innehållstyp: Publikationer

• 2010:07 Indicators of safety culture – selection and utilization of leading safety performance indicators

  Safety indicators play a role in providing information on organizational performance, motivating people to work on safety and increasing organizational potential for safety. The aim of this report is to provide an overview on leading safety indicators in the domain of nuclear safety. The report

  Innehållstyp: Publikationer

• 2009:38 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stages 14 and 15

  This report constitutes Stages 14 and 15 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Stage 14 was a full one-year project, whereas Stage 15 consisted of a half-year project. Results up to Stage 13 were

  Innehållstyp: Publikationer

• 2009:27 Analysis Strategy for Fracture Assessment of Defects in Ductile Materials

  SSM has supported research for investigating the role of secondary stresses when fracture assessments are performed for cracked structures made of ductile materials. There are evidences that indicate that some secondary stresses, such as weld residual stresses, are not as important as primary

  Innehållstyp: Publikationer